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DRAGON 3.05D, Reactor Cell Calculation System with Burnup nesc0784 DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant nea-1683 ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses nea-1916 FINPSA TRAINING 2.2.0.1 -R-, a PSA model in consisting of event trees, fault trees, and cut sets
See the Soviet-made RBMK nuclear-power reactor. This was the type of reactor involved in the Chernobyl disaster. In the Advanced Gas-cooled Reactor, a British design, the core is made of a graphite neutron moderator where the fuel assemblies are located. Carbon dioxide gas acts as a coolant and it circulates through the core, removing heat.
System 80 is a pressurized water reactor design by Combustion Engineering (which was subsequently bought by Asea Brown Boveri and eventually merged into the Westinghouse Electric Company). Three System 80 reactors were built at Palo Verde Nuclear Generating Station.
TerraPower is an American nuclear reactor design and development engineering company headquartered in Bellevue, Washington. TerraPower is developing a class of nuclear fast reactors termed traveling wave reactors (TWR). [1] TWR places a small core of enriched fuel in the center of a much larger mass of non-fissile material, in this case ...
Nuclear reactor physics is the field of physics that studies and deals with the applied study and engineering applications of chain reaction to induce a controlled rate of fission in a nuclear reactor for the production of energy.
The AP1000 design traces its history to two previous designs, the AP600 and the System 80.. The System 80 design was created by Combustion Engineering and featured a two-loop cooling system with a single steam generator paired with two reactor coolant pumps in each loop that makes it simpler and less expensive than systems which pair a single reactor coolant pump with a steam generator in each ...
The reactor core design was derived from the C-E designed Arkansas Nuclear One Unit 2, the nuclear steam supply system (NSSS) was derived from the C-E designed units at Palo Verde Nuclear Generating Station, and auxiliary plant design was derived from the earlier Unit-1 and Unit-2 at the Yeonggwang (now Hanbit) Nuclear Power Plant. [3]
The very-high-temperature reactor (VHTR) uses a graphite-moderated core with a once-through uranium fuel cycle, using helium or molten salt. This reactor design envisions an outlet temperature of 1,000°C. The reactor core can be either a prismatic-block or a pebble bed reactor design.